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1. 发明授权

US06987826B2 Maximum extended load line limit analysis for a boiling water nuclear reactor 失效
标题翻译：沸水核反应堆的最大延长载重线极限分析
公开(公告)号：US06987826B2
公开(公告)日：2006-01-17
申请号：US10748420
申请日：2003-12-30
申请人： Jose L. Casillas , Eugene C. Eckert , Phuong T. Tran
发明人： Jose L. Casillas , Eugene C. Eckert , Phuong T. Tran
IPC分类号： G21C17/00
CPC分类号： G21D3/001 , G21Y2002/203 , G21Y2004/40 , Y02E30/40
摘要： A method for expanding the operating domain of a boiling water nuclear reactor that permits safe operation of the reactor at low core flows is described. The operating domain is characterized by a map of the reactor thermal power and core flow. In an exemplary embodiment, the method for expanding the operating domain of a boiling water nuclear reactor permits operation of the reactor between about 120 percent of rated thermal power and about 85 percent of rated core flow to about 100 percent of rated thermal power and about 55 percent of rated core flow. The method includes determining an elevated load line characteristic that improves reactor performance, performing safety evaluations at the elevated load line to determine compliance with safety design parameters, and performing operational evaluations at the elevated load line. The method also includes defining a set of operating conditions for the reactor in an upper operating domain characterized by the elevated load line. Additionally, the method includes performing a detailed analysis of the performance of the core recirculation system and the system control components. further, the method provides for modifying the reactor process controls and computers to permit the reactor to operate in the expanded operating domain within predetermined safety parameters. Also, safety mitigation action setpoints are adjusted to permit reactor operation in the expanded operating domain.
摘要翻译：描述了允许在低核心流动下安全操作反应器的沸水核反应堆的操作范围的扩展方法。操作域的特征在于反应堆热功率和核心流量的映射。在一个示例性实施例中，用于扩展沸水核反应堆的操作范围的方法允许反应器的操作在约120％的额定热功率和约85％的额定核心流量之间至约100％的额定热功率和约55 额定核心流量百分比。该方法包括确定提高反应堆性能的提升的负载线特征，在升高的负载线执行安全性评估以确定与安全设计参数的一致性，以及在提升的负载线上执行操作评估。该方法还包括在由高架负载线表征的上运行区域中定义用于反应器的一组操作条件。此外，该方法包括对核心再循环系统和系统控制组件的性能进行详细分析。此外，该方法提供了修改反应器过程控制和计算机以允许反应器在预定的安全参数内在扩展的操作范围内操作。此外，调整安全减轻作用设定值以允许在扩展的操作域中的反应堆操作。

2. 发明授权

US06721383B2 Maximum extended load line limit analysis for a boiling water nuclear reactor 有权
标题翻译：沸水核反应堆的最大延长载重线极限分析
公开(公告)号：US06721383B2
公开(公告)日：2004-04-13
申请号：US09683335
申请日：2001-12-14
申请人： Jose L. Casillas , Eugene C. Eckert , Phuong T. Tran
发明人： Jose L. Casillas , Eugene C. Eckert , Phuong T. Tran
IPC分类号： G21C1700
CPC分类号： G21D3/001 , G21Y2002/203 , G21Y2004/40 , Y02E30/40
摘要： A computerized method for expanding the operating domain of a boiling water nuclear reactor that permits safe operation of the reactor at core flows lower than normal operating parameters is provided. The operating domain is characterized by a map of the reactor thermal power and core flow. The computerized method includes determining by computer simulation a load line characteristic that is elevated over normal operating parameters and that increases reactor performance over normal operating parameters, performing safety evaluations by computer simulation at the elevated load line to determine compliance with safety design parameters, and performing operational evaluations by computer simulation at the elevated load line.
摘要翻译：提供了一种用于扩展沸点核反应堆的操作范围的计算机化方法，其允许在低于正常操作参数的核心流动下安全运行反应堆。操作域的特征在于反应堆热功率和核心流量的映射。计算机化方法包括通过计算机模拟确定在正常操作参数之上升高的负载线特征，并且将反应堆性能提高到正常操作参数，通过在升高的负载线上的计算机模拟执行安全性评估以确定符合安全设计参数，以及执行在升高的负载线上通过计算机模拟进行操作评估。

3. 发明授权

US06697447B1 Maximum extended load line limit analysis for a boiling water nuclear reactor 有权
标题翻译：沸水核反应堆的最大延长载重线极限分析
公开(公告)号：US06697447B1
公开(公告)日：2004-02-24
申请号：US09475592
申请日：1999-12-30
申请人： Jose L. Casillas , Eugene C. Eckert , Phuong T. Tran
发明人： Jose L. Casillas , Eugene C. Eckert , Phuong T. Tran
IPC分类号： G21C1700
CPC分类号： G21D3/001 , G21Y2002/203 , G21Y2004/40 , Y02E30/40
摘要： A method for expanding the operating domain of a boiling water nuclear reactor that permits safe operation of the reactor at low core flows is described. The operating domain is characterized by a map of the reactor thermal power and core flow. In an exemplary embodiment, the method for expanding the operating domain of a boiling water nuclear reactor permits operation of the reactor between about 120 percent of rated thermal power and about 85 percent of rated core flow to about 100 percent of rated thermal power and about 55 percent of rated core flow. The method includes determining an elevated load line characteristic that improves reactor performance, performing safety evaluations at the elevated load line to determine compliance with safety design parameters, and performing operational evaluations at the elevated load line. The method also includes defining a set of operating conditions for the reactor in an upper operating domain characterized by the elevated load line. Additionally, the method includes performing a detailed analysis of the performance of the core recirculation system and the system control components. Further, the method provides for modifying the reactor process controls and computers to permit the reactor to operate in the expanded operating domain within predetermined safety parameters. Also, safety mitigation action setpoints are adjusted to permit reactor operation in the expanded operating domain.
摘要翻译：描述了允许在低核心流动下安全操作反应器的沸水核反应堆的操作范围的扩展方法。操作域的特征在于反应堆热功率和核心流量的映射。在一个示例性实施例中，用于扩展沸水核反应堆的操作范围的方法允许反应器的操作在约120％的额定热功率和约85％的额定核心流量之间至约100％的额定热功率和约55 额定核心流量百分比。该方法包括确定提高反应堆性能的提升的负载线特征，在升高的负载线执行安全性评估以确定与安全设计参数的一致性，以及在提升的负载线上执行操作评估。该方法还包括在由高架负载线表征的上运行区域中定义用于反应器的一组操作条件。此外，该方法包括对核心再循环系统和系统控制组件的性能进行详细分析。此外，该方法提供了修改反应器过程控制和计算机以允许反应器在预定的安全参数内在扩展的操作范围内操作。此外，调整安全减轻作用设定值以允许在扩展的操作域中的反应堆操作。

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